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Jurnal Forum Nuklir

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Published by Badan Tenaga Nuklir Nasional

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Core Subject : Science,

Materials Science & Nanotechnology

Jurnal Forum Nuklir (JFN) adalah jurnal ilmiah bertaraf nasional dengan ruang lingkup semua aspek yang terkait dengan ilmu pengetahuan nuklir, teknologi nuklir, termasuk pendidikan dan sumber daya manusia nuklir. JFN (ISSN 1978-8738) diterbitkan oleh Sekolah Tinggi Teknologi Nuklir BATAN

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Articles 6 Documents

Search results for , issue "JURNAL FORUM NUKLIR VOL 14 NO 1 MEI 2020" : 6 Documents clear

VERIFICATION OF THE DETERMINATION OF 12 MEV ELECTRON BEAM OUTPUT VERSA HD / 154714 LINEAR SPEEDING PLANE IN MAYAPADA HOSPITAL Assef Firmando Firmansyah
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 14 NO 1 MEI 2020
Publisher : BATAN

VERIFICATION OF THE DETERMINATION OF THE NOMINAL ENERGY BEAM OUTPUT OF THE 12 MEV LINEAR ACCELERATOR PLANE ELEKTA VERSA HD / 154714 AT MAYAPADA HOSPITAL. This paper describes verifying the determination of the 12 MeV nominal energy beam electron water absorption dose emitted from the Elekta Versa HD / 154714 medical linear accelerator owned by Mayapada Hospital, Lebak Bulus, Jakarta. Measurements were done in the 1D water phantom Scanner under reference conditions with the distance of the radiation source to the surface of the water 100 cm and the radiation field formed by the applicator 10 cm x 10 cm and the depth corresponding to (0.6 R50 - 0.1) cm. The IBA CC13 ionization detector is used as a radiation measurement tool for PDD measurements, while the Roos parallel ionization detector is used for absolute measurements. Roos's parallel ionizer detector is aligned with PTKMR-BATAN's PTW Webline electrometer. This detector is also traced to the primary standard laboratory of BIPM, France. Meanwhile, the PCC04 chip ionizing detector parallel to the PCC04 is coupled with a Dose 1 electrometer owned by Mayapada Hospital, which is traced to the PTB primary standard laboratory. Calculation of measurement results is carried out using the IAEA dosimetry protocol contained in Technical Report Series No. 398. The results obtained indicate a fairly good fit between the two measurements with a difference of 0.3%

Probability study of airplane crash on Kartini Reactor site area Zulfikar Erlan Bhagaskara; N N Aufanni
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 14 NO 1 MEI 2020
Publisher : BATAN

Abstract. Probability study of airplane crash at Kartini Reactor site has been carried out. Objective of this study is to determine probability of airplane crash coming from airports around Kartini Reactor site to Kartini Reactor Site. This study was carried out in several stages, namely identification of airports around Kartini Reactor site, initial screening using SDV values (10 km for small airport and 16 km for large airport), probability calculation of airplane crash at Kartini Reactor site and comparing the calculation result with applicable regulations. Based on the identification results there are four airports / runways around the Kartini Reactor site, they are Adi Sutjipto Airport, Adi Sumarmo Airport, Depok Runway, and Yogyakarta International Airport where distance from airport to the site between 2.26-48.23 km. After screening using SDV value, that is known only Adi Sutjipto Airport which is inside SDV radius of Kartini Reactor, so that probability of airplane crash from Adi Sutjipto Airport is calculated, i.e. 3,769x10-8 events/year is. This value is still under the provisions in BAPETEN Regulation No. 4 of 2018 i.e. maximum 10-7 events/year. So it can be concluded that Kartini Reactor is safe from the possibility of airplane crash.

An Analysis of Radiation Worker Safety at SAMOP Facility PSTA-BATAN Yogyakarta Using MCNP6 Suharyana Suharyana Suharyana
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 14 NO 1 MEI 2020
Publisher : BATAN

It has been done the calculation of g dose simulation received radiation worker around SAMOP using MCNP6. The fuel SAMOP was modelled on the solution of uranyl nitrate (UO2(NO3)2) with enrichment of 19.75% and a concentration of 300 g U/L. SAMOP was operated on a power of 600 watts and burn up for 6 days using ORIGEN2. From the simulation burn up acquired information g radiation contribution used to calculate the dose received by radiation workers. The Calculation of the dose rate using MCNP6 at a distance of 225 cm from SAMOP without shielding obtained the result of g dose the amount of (11,217.39 ± 0.35) mSv/hour with the estimated working time of radiation workers at 0.02 hours/week. Addition of the barite concrete shielding with a thickness of 47.69 cm at a distance of 225 cm from SAMOP using an extrapolation approach based on the variation of the shielding thickness of simulation calculation results obtained g dose rate of 5.21 mSv/hour and estimated time maximum work of 36.98 hours/week.

Evaluation of The Officer’s Behaviour in Public Services of The Nuclear Minerals Technology Madyaningarum Madyaningarum
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 14 NO 1 MEI 2020
Publisher : BATAN

Service behaviour is defined generally as service behaviour that refers to official job descriptions and service scripts and completes core service tasks using standard service procedures. Evaluation of the behaviour of service officers has the opportunity to trigger continuous improvement in service quality to improve organizational performance—primary data from 73 questionnaires, which are the result of customer satisfaction assessment of nuclear mineral technology services. Data analysis used descriptive frequency statistics that provide a typical condition of the diversity of data. The behavioural evaluation results show that service personnel is polite, not selective; all customers have the same position, officers complete services according to the agreed period, officers complete services following service requirements. This research provides evidence that uncertainty in serving customers requires frontline employees to take personal initiative to anticipate customer needs, prevent and eliminate potential obstacles in service delivery, and continuously identify new opportunities to improve service quality.

PLANTS COVERING INFLUENCE TO THE RADIOISOTOPES EXISTENCE OF Cs-137 AND Pb-210 IN THE SOIL Nita Suhartini; Barokah Aliyanta; Arief Adhari
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 14 NO 1 MEI 2020
Publisher : BATAN

PLANTS COVERING INFLUENCE TO THE RADIOISOTOPES EXISTENCE OF 137Cs and 210Pbex IN THE SOIL. Cs-137 and Pbex-210 of environmental radioisotope content in the soil can be useful to estimate the rate of erosion/deposition in an area, by comparing the inventory value of Cs-137 or Pbex-210 in observed site with those in a stable reference site. Cs-137 and Pbex-210 stick very strongly at the surface of the soil (clay), so it can use as a tracer for the movement of soil. Plants very influence the existence of Cs-137 and Pbex-210 environmental radioisotopes as a cover. If without a plant cover, then this environmental radioisotope at the soil would be gone by rain off. This experiment aims to observe the effect of plant cover on the existence of Cs-137 and Pbex-210 at the soil in uncultivated land. Sampling had been done in two uncultivated lands when the land still covering by plants (2016) and after becoming vacant land (2018), using coring (10 cm) for the surface layer and coring (7 cm) for the depth of 20 cm. The result showed that the activity of 137Cs and 210Pbex environmental radioisotopes at the surface layer decreased very significantly, and total inventory values until the depth of 20 cm decreased quite significantly at a vacant land condition. The corrosion rate for the vacant land is higher than the planted land. The value of erosion rate using the 137Cs method is 44.1 t/ha.y (CBG); -4.3t/ha.y (BMC) and 4 t/ha.y (CBG); -27.1 t/ha.y (BMC) for planted land and vacant land, respectively. Meanwhile, using the 210 Pb ex method is -8 t/ha.y (CBG); -36.9 t/ha.y (BMC) for planted land and -58 t/ha.yrs (CBG), -79.9 t/ha.yrs (BMC) for vacant land.

ANALYSIS OF HEAT AND MASS TRANSFER ON COOLING TOWER FILL Abdul Aziz Rohman Hakim; Engkos Achmad Kosasih
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 14 NO 1 MEI 2020
Publisher : BATAN

This paper discusses heat and mass transfer in cooling tower fill. In this research, dry bulb temperature at the bottom fill, ambient relative humidity, air stream velocity entering fill, dry bulb temperature leaving the fill, relative humidity of air leaving the fill, inlet and outlet water temperature of cooling tower were measured. Those data used in heat and mass transfer calculation in cooling tower fill. Then, do the heat and mass transfer calculation based on proposed approch. The results are compared with design data. The design and analogy method showed different result. The parameter which influence the heat transfer at cooling tower are represented by coefficient of heat transfer hl and coefficient of mass transfer kl. The differencies result between design and analogy method shows that there is important parameter which different. Deeply study needed for it.

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